CN104749605A - Mentoring method and device for measuring effective dose on real time - Google Patents

Mentoring method and device for measuring effective dose on real time Download PDF

Info

Publication number
CN104749605A
CN104749605A CN201310743338.1A CN201310743338A CN104749605A CN 104749605 A CN104749605 A CN 104749605A CN 201310743338 A CN201310743338 A CN 201310743338A CN 104749605 A CN104749605 A CN 104749605A
Authority
CN
China
Prior art keywords
effective dose
organ
tissue
light guide
real time
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
CN201310743338.1A
Other languages
Chinese (zh)
Other versions
CN104749605B (en
Inventor
王勇
韦应靖
黄亚雯
冯梅
李强
陈立
杨慧梅
牛蒙青
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China Institute for Radiation Protection
Original Assignee
China Institute for Radiation Protection
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by China Institute for Radiation Protection filed Critical China Institute for Radiation Protection
Priority to CN201310743338.1A priority Critical patent/CN104749605B/en
Publication of CN104749605A publication Critical patent/CN104749605A/en
Application granted granted Critical
Publication of CN104749605B publication Critical patent/CN104749605B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Landscapes

  • Measurement Of Radiation (AREA)

Abstract

The invention belongs to the radiation dose monitoring technology, and specifically relates to a monitoring method and device for measuring effective dose on real time. The method comprises the steps of manufacturing a simulated human organ or tissue model; performing monte carlo simulation calculation through a computer to obtain absorbing dose of a plurality of points in the organ or tissue model so as to obtain an average value; finding out the points in which the absorbing dose is the same as the calculated average value in the organ or tissue model; arranging a detector on the points corresponding to the organ or tissue model, wherein the measurement result represents the average absorbing dose DT, R of the organ or tissue; calculating the effective dose for a human body by the calculation formula of the effective dose E according to the weight factor wT of the organ or tissue and the selected value of the radiation weight factor wR. With the adoption of the method and the device, the effective dose for workers can be directly measured, and thus the radiation protection can be conveniently optimized.

Description

A kind ofly can be used for monitoring method and the device of measuring effective dose in real time
Technical field
The invention belongs to radiation dose monitoring technology, be specifically related to a kind of monitoring method and the device that can be used for measuring in real time effective dose.
Background technology
Along with increasing and the widespread use of nuclear technology of nuclear power plant of China, the staff accepting ionising radiation increases year by year, and people more and more pay attention to radiation proof work.In radiation protection practice, a fundamental purpose of carrying out measurements and calculations is in order to the actual radiation irradiation being subject to maybe may being subject to of quantitative explanation individual, thus need to relate to by according to the relevant radiant quantity of individual, and then extrapolate the dangerous size that Radiation On Human causes.
Radiation proof three principles are protection legitimacy, optimization and dose limits, and the amount that relevant national standard uses when prescribed dose limit value is effective dose.But up to the present, effective dose is also just applied to a key concept of radiation protection regulation, can not be real-time measure.Effective dose E is defined as:
E = Σ T w T H T = Σ T w T Σ R w R D T , R - - - ( 1 )
W tthe weight factor of tissue or organ T, w rthe weight factor of radiation R, D t,Rit is the average absorbed dose in tissue or organ T.
Average absorbed dose D in tissue or organ T t,Rbe difficult to measure, do not form effective dose Real-time Measuring Technique at present, in order to implement the management of radiation protection dosage limit value, the practical amount (as Hp (10) equivalent) of general employing is estimated.Show according to ICRP Relevant Publications and domestic and international research, in some radiation places, both gaps are comparatively large, and this brings very large puzzlement to effectively enforcement personaldoselimit and optimization of radiation protection.
Summary of the invention
The object of the invention is to the defect for prior art, a kind of monitoring method and the device that can be used for measuring in real time effective dose are provided, thus in containing the workplace of ionising radiation, directly can measure effective dose.
Technical scheme of the present invention is as follows: a kind ofly can be used for the monitoring method measuring effective dose in real time, first organ or tissue's model of simulated humanbody is made, and use computing machine to be calculated by Monte Carlo simulation, calculate the absorbing agent value of multiple point in organ or tissue's model, obtain mean value; Then, the point that the absorbing agent value in organ or tissue's model is identical with the mean value that calculating obtains is found; Be put in by detector on point corresponding to organ or tissue's model, its measurement result represents the average absorbed dose D of this organ or tissue t,R; Finally, utilize the computing formula of effective dose E, in conjunction with the weight factor w of organ or tissue tand radiation weighting factor w rselected value, calculate the effective dose of human body.
A kind ofly can be used for the monitoring device measuring effective dose in real time, comprise artificial human body model, multiplexed detection device system and computing machine, wherein, described multiplexed detection device system is made up of multiplexed detection passage and data acquisition process unit, each road detection channels comprises the plastic scintillant be placed in artificial human body model, described plastic scintillant is connected with photomultiplier by optical fiber, and photomultiplier is by prime amplifier connection data acquisition process unit; Described data acquisition process unit is connected with for the computing machine that Monte Carlo simulation calculates and effective dose calculates.
Further, can be used for the monitoring device measuring effective dose in real time as above, wherein, between described plastic scintillant and optical fiber, be provided with the first conical light guide, between the rounded bottom surface of plastic scintillant and the first conical light guide, be provided with the first articulamentum; Between described optical fiber and photomultiplier, be provided with the second conical light guide, between the rounded bottom surface of photomultiplier and the second conical light guide, be provided with the second articulamentum.
Further, the first described articulamentum and the material of the second articulamentum are methyl-silicone oil, and the first described conical light guide and the material of the second conical light guide are PMMA.
Further, can be used for the monitoring device measuring effective dose in real time as above, wherein, be provided with the polyvinyl resin layer of black outside described plastic scintillant, between polyvinyl resin layer and plastic scintillant, be provided with aluminium foil.
Further, can be used for the monitoring device measuring effective dose in real time as above, wherein, be respectively equipped with the polyvinyl resin layer of black outside the first described conical light guide and the second conical light guide, between polyvinyl resin layer and the first conical light guide or the second conical light guide, be provided with aluminium foil.
Beneficial effect of the present invention is as follows: the present invention utilizes manikin manufacturing technology, Monte Carlo simulation technique and fiber-optic probe technology, forms the method can measuring effective dose in real time.The device formed by the method is made up of manikin, multiplexed detection device system and computing machine, can be applicable in the place of ionising radiation, directly measures the effective dose that staff is subject to, and brings great convenience for implementing optimization of radiation protection.
Accompanying drawing explanation
Fig. 1 is the structural representation of monitoring device of the present invention;
Fig. 2 is the structural representation of detection channels.
Embodiment
Below in conjunction with accompanying drawing and implementation process, the present invention is described in detail.
Along with increasing and the widespread use of nuclear technology of nuclear power plant of China, the staff accepting ionising radiation increases year by year, and people more and more pay attention to radiation proof work.Effective dose, as radiation proof fundamental quantity, is the basis of implementing personaldoselimit and optimization of radiation protection, the technical sophistication measured effective dose relate to because real-time, and difficulty is large, does not also measure the instrument of effective dose at present in real time.The invention provides a kind of method and device, in containing the workplace of ionising radiation, directly can measure effective dose.
According to the formula (1) in background technology, the difficult point of measurement effective dose is the average absorbed dose D in tissue or organ T in real time t,Rbe not easy real-time measurement.In order to solve the difficult problem that effective dose is measured in real time, first D will be realized t,Rreal-time measurement.
Absorbed dose be defined as ionising radiation give unit mass material on average authorize can, under energy and fluence distribute identical radiation event, but for the material of same volume unlike material, its absorbed dose is different.Measure the average absorbed dose D in tissue or organ T t,Rmainly contain two difficult problems:
1) directly go measurement in tissue or organ unrealistic;
2) absorbed dose for certain a bit, wants to be organized or the average absorbed dose of organ, need the absorbed dose of measurement multiple spot, then obtain mean value, surveying work amount very large.
In order to deal with problems 1), can artificial human body model be used, then detector is put in the organ or tissue of the emulation in manikin, tissue or intraorganic absorbed dose can be obtained.Current manikin manufacturing technology is comparatively ripe, the organ or tissue of emulation, and in tissue equivalent's degree, fundamental sum human body situation is identical, and the accuracy adopting this method to measure tissue or organ internal absorbed dose can be guaranteed.
In order to put the axe in the helve 2), adopt the method for representative point.In Ji Zhaochu organ or tissue certain a bit, the equal absorbing agent value of absorbing agent value peace on this aspect is equal.Along with the development of Monte Carlo simulation technique, analog computation result can be accomplished very accurate.Can trust so adopt Monte Carlo method to find representative point.First use computing machine to set up manikin, calculated by Monte Carlo simulation, calculate the absorbing agent value of many points in organ or tissue, after obtaining mean value, find out the point that absorbing agent value is identical with mean value.After finding this point, be put in by detector in this point of organ or tissue, its measurement result just represents the average absorbed dose D of this organ or tissue t,R.
For different radiation, according to the average absorbed dose D of the human organ measured or tissue t,R, the data of associative list 1 and table 2, recycling formula (1) directly can obtain effective dose.
The weight factor w of table 1 human organ or tissue t
* No. ICRP103 report is derived from
Table 2 radiation weighting factor w r
* No. ICRP103 report is derived from
w R = 2.5 + 18.2 e - [ ln ( E n ) ] 2 / 6 , E n < 1 MeV 5.0 + 17.0 e - [ ln ( 2 E n ) ] 2 / 6 , 1 MeV &le; E n &le; 50 MeV 2.5 + 3.25 e - [ ln ( 0.04 E n ) ] 2 / 6 , E n > 50 MeV - - - ( 2 )
Wherein, En is the energy of neutron, i.e. the radiation weighting factor w of neutron rrelevant with the energy of neutron.
As shown in Figure 1, rely on measuring method provided by the invention, the measurement mechanism of formation is made up of artificial human body model, multiplexed detection device system and computing machine.Wherein multiplexed detection system is made up of multichannel measurement passage and data acquisition process unit.Each road detection channels is made up of plastic scintillant, Transmission Fibers, photomultiplier, prime amplifier.
In artificial human body model, according to the situation of table 1 tissue weighting factor, the tissue that tissue weighting factor is larger or organ, its emulator wants high, comprises red marrow, colon, lung, stomach, breast, sexual gland, bladder, esophagus, liver, thyroid gland.The tissue less to tissue weighting factor or organ as bone surface, brain, glandula, skin, w tbe only 0.01, together with other parts of health, can using-system equivalent material during making, need not distinguish in artificial human body model.
In order to measure the absorbed dose of tissue or organ in artificial human body model accurately, detection system should possess very high sensitivity.Multiplexed detection system has 28 Measurement channel and 1 data acquisition process unit, and every 1 road detection channels is made up of plastic scintillant, Transmission Fibers, photomultiplier, prime amplifier.The structure of detection channels is shown in Fig. 2.In Fig. 2,1 is plastic scintillant, and 2 and 6 is articulamentum, and 3 and 5 is pyramid type photoconduction, and 4 is Transmission Fibers, and 7 is photomultiplier.The material of articulamentum is methyl-silicone oil, and light-guide material is PMMA.
The advantage that Measurement channel designs like this is: it is very little that plastic scintillant can do, and volume is 6cm 3right cylinder, be conveniently placed in Human autopsy tissues, to measure the absorbed dose of certain organ or tissue of human body, the photon signal of generation reaches via optical fiber and externally carries out signal transacting, and optical fiber is long is 3m.So just achieve the measurement of human body internal absorbed dose.
The distribution situation of detector in artificial human body model is as follows:
(1) red marrow, colon, lung, stomach, breast, sexual gland, bladder, esophagus, liver, thyroid gland respectively places 2 detectors.
Because the tissue weighting factor of these organ or tissues is comparatively large, detector can only be placed on some positions limited in organ or tissue.So just can not find that point identical with mean value, the value namely on a point is not enough to replace mean value, uses the value of a point to have larger error, therefore, uses the mean value of two points to replace the mean value of whole organ or tissue more accurate.
Picture lung, sexual gland, breast, liver, thyroid gland respectively has 2 in human body, and 2 detectors are placed on above the organ of left and right respectively.Red marrow, colon, stomach, bladder, esophagus in vivo shared volume is comparatively large, and 2 detectors are placed on 2 points different in organ.
(2) on spinal bone surface, brain, glandula, and skin of chest respectively places 1 detector, 1 detector is respectively placed at both legs and both arms muscle place.
Altogether need 28 detectors, form 28 Measurement channel, this 28 road signal can by after the unified process of 1 data cell, obtain the step-by-step counting of each detector, the absorbed dose of this step-by-step counting and detector place human organ or tissue is proportional, scale-up factor can obtain through Calibration Experiment, can obtain the absorbed dose of detector place organ or tissue like this, more just can obtain effective dose according to formula (1) according to counting.Obtain this computation process of effective dose by step-by-step counting to be completed by computing machine, effective dose result is output to display display.
Measurement channel selects plastic scintillant, and be because the element composition of plastic scintillant and density are similar to identical with human body soft tissue, in radiation protection, think that plastic scintillant possesses good tissue equivalent's property, its dosage effect and tissue are similar to.After the ionising radiations such as gamma-rays enter plastic scintillant, make scintillator atomic excitation, the atom excited produces scintillation photons, i.e. visible ray when de excitation.Visible ray is collected by optical fiber through articulamentum and photoconduction, and then scintillation photons is through Optical Fiber Transmission, is collected into the photocathode of photomultiplier, produces light signal by photoelectric effect by photoconduction and articulamentum, by follow-up electronic system Treatment Analysis.
Be surrounded by polyvinyl resin and the aluminium foil of black outside plastic scintillant, polyvinyl resin is positioned at outermost layer, gets to the visible ray of scintillator for absorbing the external world, prevents visible ray from entering scintillator; Aluminium foil is positioned at polyvinyl resin layer, is close to scintillator as reflection horizon, in order to strengthen the reflection of scintillation photons on border, reduces the ratio of scintillation photons injection scintillator, improves the intensity of signal.
Articulamentum uses methyl-silicone oil, is totally reflected at interface in order to reduce scintillation photons, increases the collection efficiency of scintillation photons.Photoconduction is PMMA material, makes pyramid type, for by the photon collection of scintillator to optical fiber, it is outer the same with plastic scintillant, is surrounded by one deck aluminium foil and black polyethylene resin.
Obviously, those skilled in the art can carry out various change and modification to the present invention and not depart from the spirit and scope of the present invention.Like this, if these amendments of the present invention and modification belong within the scope of the claims in the present invention and equivalent technology thereof, then the present invention is also intended to comprise these change and modification.

Claims (7)

1. one kind can be used for the monitoring method measuring effective dose in real time, it is characterized in that: the organ or tissue's model first making simulated humanbody, and use computing machine to be calculated by Monte Carlo simulation, calculate the absorbing agent value of multiple point in organ or tissue's model, obtain mean value; Then, the point that the absorbing agent value in organ or tissue's model is identical with the mean value that calculating obtains is found; Be put in by detector on point corresponding to organ or tissue's model, its measurement result represents the average absorbed dose D of this organ or tissue t,R; Finally, utilize the computing formula of effective dose E, in conjunction with the weight factor w of organ or tissue tand radiation weighting factor w rselected value, calculate the effective dose of human body.
2. one kind can be used for the monitoring device measuring effective dose in real time, comprise artificial human body model, multiplexed detection device system and computing machine, it is characterized in that: described multiplexed detection device system is made up of multiplexed detection passage and data acquisition process unit, each road detection channels comprises the plastic scintillant be placed in artificial human body model, described plastic scintillant is connected with photomultiplier by optical fiber, and photomultiplier is by prime amplifier connection data acquisition process unit; Described data acquisition process unit is connected with for the computing machine that Monte Carlo simulation calculates and effective dose calculates.
3. can be used for the monitoring device measuring effective dose in real time as claimed in claim 2, it is characterized in that: between described plastic scintillant and optical fiber, be provided with the first conical light guide, between the rounded bottom surface of plastic scintillant and the first conical light guide, be provided with the first articulamentum.
4. can be used for the monitoring device measuring effective dose in real time as claimed in claim 2 or claim 3, it is characterized in that: between described optical fiber and photomultiplier, be provided with the second conical light guide, between the rounded bottom surface of photomultiplier and the second conical light guide, be provided with the second articulamentum.
5. can be used for the monitoring device measuring effective dose in real time as claimed in claim 4, it is characterized in that: the first described articulamentum and the material of the second articulamentum are methyl-silicone oil, the first described conical light guide and the material of the second conical light guide are PMMA.
6. can be used for the monitoring device measuring effective dose in real time as claimed in claim 2, it is characterized in that: the polyvinyl resin layer being provided with black outside described plastic scintillant, is provided with aluminium foil between polyvinyl resin layer and plastic scintillant.
7. can be used for the monitoring device measuring effective dose in real time as claimed in claim 5, it is characterized in that: the polyvinyl resin layer being respectively equipped with black outside the first described conical light guide and the second conical light guide, is provided with aluminium foil between polyvinyl resin layer and the first conical light guide or the second conical light guide.
CN201310743338.1A 2013-12-30 2013-12-30 A kind of monitoring method can be used for real-time measurement effective dose and device Active CN104749605B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201310743338.1A CN104749605B (en) 2013-12-30 2013-12-30 A kind of monitoring method can be used for real-time measurement effective dose and device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201310743338.1A CN104749605B (en) 2013-12-30 2013-12-30 A kind of monitoring method can be used for real-time measurement effective dose and device

Publications (2)

Publication Number Publication Date
CN104749605A true CN104749605A (en) 2015-07-01
CN104749605B CN104749605B (en) 2019-01-04

Family

ID=53589578

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201310743338.1A Active CN104749605B (en) 2013-12-30 2013-12-30 A kind of monitoring method can be used for real-time measurement effective dose and device

Country Status (1)

Country Link
CN (1) CN104749605B (en)

Cited By (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105549063A (en) * 2015-12-30 2016-05-04 黑龙江省中贝技术有限公司 Detection method realized by use of plastic scintillator detector
CN105866816A (en) * 2016-05-11 2016-08-17 西北核技术研究所 Detector for monitoring effective space-proton-radiation dose and detector obtaining method
CN105891868A (en) * 2016-04-12 2016-08-24 哈尔滨易奥秘科技发展有限公司 Double-fluorescent material radiation dose detection optical fiber probe
CN106932810A (en) * 2017-04-01 2017-07-07 西安体医疗科技有限公司 A kind of convolutional calculation method of gamma rays dosage
CN107290774A (en) * 2017-07-21 2017-10-24 四川瑶天纳米科技有限责任公司 Neutron dose fast determination method
WO2017206485A1 (en) * 2016-06-01 2017-12-07 南京中硼联康医疗科技有限公司 Radiation dose measuring method
CN108535769A (en) * 2017-03-03 2018-09-14 中国辐射防护研究院 A kind of probe and its test calibration method tested for optical fiber neutron detection system with calibration
CN108572387A (en) * 2017-03-07 2018-09-25 中国辐射防护研究院 A kind of body source measures the calibration method of detector
CN108983273A (en) * 2018-08-22 2018-12-11 中国辐射防护研究院 A kind of real-time measurement system and method for the distribution of inside of human body 3-dimensional dose
CN109106452A (en) * 2018-10-11 2019-01-01 中国疾病预防控制中心辐射防护与核安全医学所 It is a kind of for measuring the fixation bracket of human thyroglobulin iodine
CN110146912A (en) * 2019-05-30 2019-08-20 吉林大学 A kind of detection method and device of the Dose enhancement factors factor for 60Co gamma-ray irradiation source
CN111308538A (en) * 2020-03-11 2020-06-19 江苏超敏科技有限公司 Detection equipment for simulating radiation environment of space station to damage human body
CN113866811A (en) * 2021-08-12 2021-12-31 中国辐射防护研究院 Improved processing method of silicon-based micro-dosimeter

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0197892A (en) * 1987-10-09 1989-04-17 Hamamatsu Photonics Kk Nuclide distinguishable dose measuring method and its device
US20120157445A1 (en) * 2010-12-17 2012-06-21 The Board Of Trustees Of The Leland Stanford Junior University Cognitive Function
CN103394167A (en) * 2013-08-01 2013-11-20 山东省肿瘤医院 BED (biological effective dose)-based prediction method for complications caused by tumor radiotherapy

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0197892A (en) * 1987-10-09 1989-04-17 Hamamatsu Photonics Kk Nuclide distinguishable dose measuring method and its device
US20120157445A1 (en) * 2010-12-17 2012-06-21 The Board Of Trustees Of The Leland Stanford Junior University Cognitive Function
CN103394167A (en) * 2013-08-01 2013-11-20 山东省肿瘤医院 BED (biological effective dose)-based prediction method for complications caused by tumor radiotherapy

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
席德明 等: "《常用核电子技术》", 31 January 1982 *
白玫 等: "两种介入放射学(CA和PTCA)所致患者辐射剂量研究", 《中国医学影像技术》 *

Cited By (24)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105549063A (en) * 2015-12-30 2016-05-04 黑龙江省中贝技术有限公司 Detection method realized by use of plastic scintillator detector
CN105891868A (en) * 2016-04-12 2016-08-24 哈尔滨易奥秘科技发展有限公司 Double-fluorescent material radiation dose detection optical fiber probe
CN105891868B (en) * 2016-04-12 2018-11-06 哈尔滨易奥秘科技发展有限公司 A kind of double fluorescent material dose of radiation detection fiber probes
CN105866816A (en) * 2016-05-11 2016-08-17 西北核技术研究所 Detector for monitoring effective space-proton-radiation dose and detector obtaining method
CN105866816B (en) * 2016-05-11 2018-07-17 西北核技术研究所 Monitor the detector and detector acquisition methods of Spacial Proton radiation effective dose
US10379227B2 (en) 2016-06-01 2019-08-13 Neuboron Medtech Ltd. Radiation dose measuring method
WO2017206485A1 (en) * 2016-06-01 2017-12-07 南京中硼联康医疗科技有限公司 Radiation dose measuring method
CN107450090A (en) * 2016-06-01 2017-12-08 南京中硼联康医疗科技有限公司 Radiation dose measurement method
CN110244339A (en) * 2016-06-01 2019-09-17 南京中硼联康医疗科技有限公司 Radiation dose measurement method
CN108535769B (en) * 2017-03-03 2022-06-07 中国辐射防护研究院 Probe for testing and calibrating optical fiber neutron detection system and testing and calibrating method thereof
CN108535769A (en) * 2017-03-03 2018-09-14 中国辐射防护研究院 A kind of probe and its test calibration method tested for optical fiber neutron detection system with calibration
CN108572387A (en) * 2017-03-07 2018-09-25 中国辐射防护研究院 A kind of body source measures the calibration method of detector
CN108572387B (en) * 2017-03-07 2023-07-14 中国辐射防护研究院 Calibration method of body source measurement detector
CN106932810A (en) * 2017-04-01 2017-07-07 西安体医疗科技有限公司 A kind of convolutional calculation method of gamma rays dosage
CN107290774A (en) * 2017-07-21 2017-10-24 四川瑶天纳米科技有限责任公司 Neutron dose fast determination method
CN108983273B (en) * 2018-08-22 2021-09-24 中国辐射防护研究院 Real-time measurement system and method for three-dimensional dose distribution in human body
CN108983273A (en) * 2018-08-22 2018-12-11 中国辐射防护研究院 A kind of real-time measurement system and method for the distribution of inside of human body 3-dimensional dose
CN109106452B (en) * 2018-10-11 2020-06-19 中国疾病预防控制中心辐射防护与核安全医学所 Fixing support for measuring human body thyroid iodine
CN109106452A (en) * 2018-10-11 2019-01-01 中国疾病预防控制中心辐射防护与核安全医学所 It is a kind of for measuring the fixation bracket of human thyroglobulin iodine
CN110146912A (en) * 2019-05-30 2019-08-20 吉林大学 A kind of detection method and device of the Dose enhancement factors factor for 60Co gamma-ray irradiation source
CN111308538A (en) * 2020-03-11 2020-06-19 江苏超敏科技有限公司 Detection equipment for simulating radiation environment of space station to damage human body
CN111308538B (en) * 2020-03-11 2022-03-18 江苏超敏科技有限公司 Detection equipment for simulating radiation environment of space station to damage human body
CN113866811A (en) * 2021-08-12 2021-12-31 中国辐射防护研究院 Improved processing method of silicon-based micro-dosimeter
CN113866811B (en) * 2021-08-12 2024-01-23 中国辐射防护研究院 Improved silicon-based micro-dosimeter processing technique

Also Published As

Publication number Publication date
CN104749605B (en) 2019-01-04

Similar Documents

Publication Publication Date Title
CN104749605A (en) Mentoring method and device for measuring effective dose on real time
CN102608649B (en) Statistics distributed gamma or X ray energy spectrum unscrambling method
CN104166153B (en) The measuring method of the two dimension angular distribution of radioactive substance radiation dose rate and equipment
Zarifi et al. Characterization of prompt gamma-ray emission with respect to the Bragg peak for proton beam range verification: A Monte Carlo study
CN101477203A (en) Resolution Monte Carto dosage computing method
Culbertson et al. In-phantom characterisation studies at the Birmingham Accelerator-Generated epIthermal Neutron Source (BAGINS) BNCT facility
CN104267425A (en) Method for determining detection efficiency of internal exposure HPGe detector based on CT data
CN102034266A (en) Rapid sparse reconstruction method and equipment for exciting tomography fluorescence imaging
CN107688195A (en) The method and apparatus for rebuilding the power spectrum that detector is detected
CN102928866B (en) Method for measuring spectrum and accumulated dose of neutrons by utilizing passive detector
CN107544086A (en) Gamma photon detecting and imaging device and method
Hoerner et al. Characterizing energy dependence and count rate performance of a dual scintillator fiber‐optic detector for computed tomography
Priyada et al. Use of prompt gamma emissions from polyethylene to estimate neutron ambient dose equivalent
Minsky et al. Experimental feasibility studies on a SPECT tomograph for BNCT dosimetry
CN108287357A (en) A kind of source peak detection efficient acquisition methods of cylinder bulk detector to point source
CN105866816A (en) Detector for monitoring effective space-proton-radiation dose and detector obtaining method
CN116008320A (en) Waste bin SGS (service gas station) efficiency calibration method based on Meng Ka simulation and function model
Guérin et al. Field gamma spectrometry, Monte Carlo simulations and potential of non-invasive measurements
Zhao et al. Feasibility study on neutron energy spectrum measurement utilizing prompt gamma-rays
Bartesaghi et al. Evaluation of all dose components in the LVR-15 reactor epithermal neutron beam using Fricke gel dosimeter layers
Peloso et al. Application of the HICAM camera for imaging of prompt gamma rays in measurements of proton beam range
CN104597472A (en) Method for measuring the wound radionuclide contamination depth, radionuclide variety and activity
RU2505841C1 (en) Method of measuring radiation intensity
Myers et al. Compton scattering from Li 6 at 86 MeV
Brown et al. Modelling the response of CLLBC (Ce) and TLYC (Ce) SiPM-based radiation detectors in mixed radiation fields with Geant4

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant